ML18079A795
| ML18079A795 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/09/1979 |
| From: | Librizzi F Public Service Enterprise Group |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18079A796 | List: |
| References | |
| LCR-79-06B, LCR-79-6B, NUDOCS 7908140732 | |
| Download: ML18079A795 (2) | |
Text
Public Service Electric and Gas ~ompany 80 Park Place Newark, N.J. 07101 Phone 201/430-7000 August 9, 1979 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Attention:
Mr. Albert Schwencer, Chief Operating Reactors Branch #1.
Division of Operating Reactors Gentlemen:
REVISED CYCLE 2 RELOAD ANALYSIS FACILITY OPERATING LICENSE DPR-70 UNIT NO. 1 SALEM GENERATING STATION DOCKET NO. 50-272 Ref. LCR 79-06B Salem Unit No. 1 is currently in its first refueling outage.
Cycle 1 operation was terminated with a cycle burnup of 15,439 MWD/MTU.
The reactor core is reloaded and startup of cycle 2 is expected to occur in early September 1979.
During the current refueling outage two events (fuel assembly grid strap damage and control rod damage) have caused us to change our original fuel loading plan for cycle 2 as presented to you in our letters dated March 2, 1979 and April 30, 1979.
The reload analysis summarized in this letter was performed on the as loaded core, including the additional BPRA loaded in core loca-tion F-7 (see attached core loading maps).
The Salem No. 1, cycle 2 reload core was designed such that those incidents analyzed and reported in the Salem FSAR which could potentially be affected by the fuel reload have been reviewed for the cycle 2 design.
The codes and methods used in the analysis of this reload core have all been used as part of the Westing-house standard design and safety methodology in support of re-loads previously licensed.
The safety analysis codes used for this reload are the same as those used to analyze the initial core as documented in the Salem FSAR.
The results of the safety analysis for Salem 1 cycle 2 have shown that the safety limits as contained in the FSAR are met.
- ()(JJ 790§14g?.,3,,4 5 I
't I 95-2001 (300M) 1-79 1879 1979 8-9-79 During this outage thirty (30) steam generator tubes were plugged which is significantly less than the one percent assumed in the LOCA evaluation.
The total peaking factor envelope is the same in both cycle 1 and cycle 2 with the exception of the elevated third line segment of the K(Z) curve as discussed in our letter dated April 30, 1979.
The following were changes in the kinetics parameters from cycle 1 to cycle 2:
- 1.
The Doppler Temperature Coefficient was from -2.0 to
-1.0 (pcm/°F) in cycle 1 and is from -2.9 to -1.0 (pcm/°F) in cycle 2.
Because of the small change in this parameter and the relative insensitivity of this parameter on the accident analyses, it was concluded that the change in the Doppler Temperature Coefficient would have a negligible impact on the accident analysis.
- 2.
The minimum Beff for Rod Ejection was 0.55% in cycle 1 and is 0.52% in cycle 2.
The rod ejection cases were reanalyzed to ensure that the fuel and clad limits were not exceeded.
The results show that the fuel rod at the hot spot does not exceed the limiting criteria.
In accordance with the Atomic Energy Act of 1954, as amended and the regulations thereunder, we hereby transmit copies of our re-quest for amendment and our analysis of the changes to Facility Operating License DPR-70 for Salem Generating Station Unit No. 1.
This request consists of revisions to the proposed changes to the Safety Technical Specifications (Appendix A) submitted in our letter dated March 2, 1979.
These revisions pertain to the fol-lowing areas:
Heat Flux Hot Channel Factor -
FQ (Z) (section on Fxy limits only, including the results of the r~vised 18 cases" analysis) and Nuclear Enthalpy Hot Channel Factor -
pNH.
All of the other proposed changes submitted on March 2, 1979 remain as originally submitted.
This submittal includes three signed originals and 40 copies.
Very truly yours, 6{[ J~/
' Vl L (hi a
P. Lib zi General Manager -
Electric Production